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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217H6341999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld ML20217H6251999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld ML20217F4301999-10-14014 October 1999 Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1 ML20217D3191999-10-12012 October 1999 Submits Request for Addl Info Re Licensee 990707 Proposed License Amend to Revise Min Critical Power Ratio.Listed Questions Were Discussed with Util in 991001 Telcon ML20217C1671999-10-0808 October 1999 Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2 ML20217A7601999-10-0606 October 1999 Forwards Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20212M0931999-10-0404 October 1999 Refers to 990922-23 Meeting Conducted by Region II at LaSalle Nuclear Power Station.Purpose of Visit,To Meet with Licensee Risk Mgt Staff to Discuss Util Initiatives in Risk Area & to Establish Dialog Between SRAs & Risk Mgt Staff 05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999 Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20217A6201999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issue Matrix & Insp Plan Encl ML20212E7171999-09-22022 September 1999 Forwards RAI Re Requesting Approval of License Amend to Use Different Methodology & Acceptance Criteria for Reassessment of Certain Masonry Walls Subjected to Transient HELB Pressurization Loads 05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl ML20212C0591999-09-17017 September 1999 Informs That NRC Reviewed Licensee Justifications for Deviations from NEDO-31558 & Determined That Justifications acceptable.Post-accident Neutron Flux Monitoring Instrumentation Acceptable Alternative to Reg Guide 1.97 ML20212A3581999-09-13013 September 1999 Confirms That Fuel MCPR Data for LaSalle County Station,Unit 1,Cyle 9,sent by Ltr Meets Condition 2,as Stated in 970509 NRC Ltr ML20211Q9911999-09-10010 September 1999 Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring ML20212A1141999-09-10010 September 1999 Forwards RAI Re Licensee 990519 Amend Request,Which Proposed to Relocate Chemistry TSs from TS to licensee-controlled Documents.Response Requested by 990930,so That Amend May Be Issued to Support Upcoming Unit 1 Refueling Outage ML20211P2211999-09-0808 September 1999 Forwards Insp Repts 50-373/99-14 & 50-374/99-14 on 990809- 13.No Violations Noted.Insp Concluded That Emergency Preparedness Program Maintained in Good State of Operational Readiness ML20212A8571999-09-0707 September 1999 Informs That Proprietary Document, Power Uprate SAR for LaSalle County Station,Units 1 & 2, Rev 2,Class III, NEDC-32701P,submitted in ,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20211Q6861999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant License Applicants During Wks of 001113 & 20. Validation of Exam Will Occur at Station During Wk of 001023 05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl ML20211M1151999-08-31031 August 1999 Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006 ML20211G1831999-08-27027 August 1999 Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211F8731999-08-25025 August 1999 Forwards Insp Repts 50-373/99-13 & 50-374/99-13 on 990804-06 & 09-11.No Violations Noted.Fire Protection Program Strengths Includes Low Number of Fire Protection Impairments & Excellent Control of Transient Combustibles ML20210U3201999-08-17017 August 1999 Forwards Insp Repts 50-373/99-12 & 50-374/99-12 on 990623-0728.No Violations Noted ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed ML20210E0501999-07-22022 July 1999 Submits Summary of 990630 Management Meeting Re Licensee Performance Activities Since Start Up of Unit 2.List of Attendees & Matl Used in Presentation Enclosed ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20209H5171999-07-15015 July 1999 Discusses 990701 Telcon Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at LaSalle County Nuclear Generating Station for Weeks of 990913,1018 & 1129 ML20209G4031999-07-14014 July 1999 Forwards Insp Repts 50-373/99-11 & 50-374/99-11 on 990614-18.No Violations Noted ML20209E1211999-07-14014 July 1999 Submits mid-cycle Rev of COLR IAW LaSalle County Tech Spec 6.6.A.6.d.Rev to COLR Was Necessary Due to Implementation of TS Change Approved by Ltr Dtd 990212,which Changed Turbine Stop Valve & Turbine Control Valve Scram ML20209F6931999-07-13013 July 1999 Forwards Insp Repts 50-373/99-04 & 50-374/99-04 on 990513-0622.No Violations Noted.Determined That Multiple Challenges to Main Control Room Operators Occurred During Insp Period Due to Human Performance Weaknesses ML20210C1521999-07-0909 July 1999 Forwards Post-Outage (90 Day) Summary Rept for ISI Examinations & Repair/Replacement Activities Conducted from Beginning of First Insp Period of Second ten-yr Insp Interval Through L2R07 Refueling Outage ML20209G3901999-07-0909 July 1999 Informs NRC of Status of Commitments & Requests NRC Concurrence for Use of ASME Section III App F Acceptance Criteria to Permanently Qualify Units 1 & 2 Penetrations M-49 & M-50 ML20209E0341999-07-0909 July 1999 Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101 ML20209E0361999-07-0808 July 1999 Forwards LaSalle County Station Unit 2 Cycle 8 Startup Test Rept Summary,Iaw TS NPF-18,Section 6.6.A.1.Startup Test Program Was Satisfactorily Completed on 990501 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20196J4711999-06-30030 June 1999 Discusses Closure of GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Units 1 & 2 ML20212J0311999-06-21021 June 1999 Informs of Actions Taken to Close Remaining Open Items in .Attachment Provides Detailed Justification for Closure of Open Items in Sections 5.2.2 & 5.2.8 ML20196B1951999-06-18018 June 1999 Informs NRC That Do Werts,License OP-30373-2,no Longer Requires Use of NRC License for LaSalle County Station. License May Be Terminated ML20195J7761999-06-15015 June 1999 Submits Request Relief CR-23,requesting Relief from Code Required Selection & Examinations of Noted Integral Attachments & Proposes to Utilize Alternative Selection & Examination Requirements Similar to Code Case N-509 ML20196G8021999-06-15015 June 1999 Requests Renewal of SRO License for Vv Masterson.Current License for Vv Masterson Will Expire Jul 1999.NRC Forms 398 & 396,encl.Without Encls ML20195G7101999-06-11011 June 1999 Informs That Effective 990514,GH Mccallum,License SOP-31412, No Longer Requires Use of NRC License for LaSalle Station. License Should Be Terminated ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207D2821999-05-27027 May 1999 Requests That Implementation Date for Unit 1 Be Changed Prior to Startup for L1C10 to Allow Best Allocation of Resources to Implement Unit 1 Amend Prior to Startup for Either L1C9 or L1C10.Unit 2 Will Implement Mod IAW Request 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217H6251999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for MR Kahn,Aj Mclaughlin,De Montgomery & Kr Murphy Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC from 396 Encl.Proprietary Info Withheld ML20217H6341999-10-15015 October 1999 Requests Renewal of Operator Licenses for Listed Personnel. Current Licenses for Kh Curran,Lm Gerlach,Rc Weber & Bt Rhodes Will Expire in Nov 1999.Proprietary NRC Form 398 & NRC Form 396 Encl.Proprietary Info Withheld ML20217F4301999-10-14014 October 1999 Responds to 991012 Rai,Based on 991001 Telcon Re Suppl to Request for TS Change to Revise MCPR Safety Limit & Add Approved Siemens Topical Rept for LaSalle County Station, Unit 1 ML20217C1671999-10-0808 October 1999 Provides Suppl to RAI for Approval of Unreviewed Safety Question Re Assessment of Certain safety-related Concrete Block Walls at LaSalle County Station,Units 1 & 2 05000373/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl1999-10-0404 October 1999 Forwards LER 99-003-00 IAW 10CFR50.73(a)(2)(iv).Commitments for Submittal Also Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr 05000374/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl1999-09-20020 September 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(iv).Commitments Made by Util Are Encl ML20211Q9911999-09-10010 September 1999 Informs That License SOP-4048-4,for Wp Sly May Be Terminated Due to Individual Retiring 05000374/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl1999-09-0303 September 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Encl ML20211M1151999-08-31031 August 1999 Requests That Following Eleven Individuals Take BWR Gfes of Written Operator Licensing Exam to Be Administered on 991006 ML20211G1831999-08-27027 August 1999 Provides Addl Clarification of Proposed Refueling Practices Under Proposed Core Alterations Definition Re 990813 Application for Amend to TS ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 05000373/LER-1999-002, Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed1999-07-23023 July 1999 Forwards LER 99-002-00,IAW 10CFR50.73(a)(2)(i).Commitments Made by Util Are Listed ML20209E1211999-07-14014 July 1999 Submits mid-cycle Rev of COLR IAW LaSalle County Tech Spec 6.6.A.6.d.Rev to COLR Was Necessary Due to Implementation of TS Change Approved by Ltr Dtd 990212,which Changed Turbine Stop Valve & Turbine Control Valve Scram ML20210C1521999-07-0909 July 1999 Forwards Post-Outage (90 Day) Summary Rept for ISI Examinations & Repair/Replacement Activities Conducted from Beginning of First Insp Period of Second ten-yr Insp Interval Through L2R07 Refueling Outage ML20209E0341999-07-0909 July 1999 Provides NRC with Siemens Power Corp (SPC) Fuel & GE Fuel MCPR Data for LaSalle Unit 1 Cycle 9.LaSalle Unit 1 Is Currently Scheduled to Start Cycle 9 in 991101 ML20209G3901999-07-0909 July 1999 Informs NRC of Status of Commitments & Requests NRC Concurrence for Use of ASME Section III App F Acceptance Criteria to Permanently Qualify Units 1 & 2 Penetrations M-49 & M-50 ML20209E0361999-07-0808 July 1999 Forwards LaSalle County Station Unit 2 Cycle 8 Startup Test Rept Summary,Iaw TS NPF-18,Section 6.6.A.1.Startup Test Program Was Satisfactorily Completed on 990501 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20212J0311999-06-21021 June 1999 Informs of Actions Taken to Close Remaining Open Items in .Attachment Provides Detailed Justification for Closure of Open Items in Sections 5.2.2 & 5.2.8 ML20196B1951999-06-18018 June 1999 Informs NRC That Do Werts,License OP-30373-2,no Longer Requires Use of NRC License for LaSalle County Station. License May Be Terminated ML20196G8021999-06-15015 June 1999 Requests Renewal of SRO License for Vv Masterson.Current License for Vv Masterson Will Expire Jul 1999.NRC Forms 398 & 396,encl.Without Encls ML20195J7761999-06-15015 June 1999 Submits Request Relief CR-23,requesting Relief from Code Required Selection & Examinations of Noted Integral Attachments & Proposes to Utilize Alternative Selection & Examination Requirements Similar to Code Case N-509 ML20195G7101999-06-11011 June 1999 Informs That Effective 990514,GH Mccallum,License SOP-31412, No Longer Requires Use of NRC License for LaSalle Station. License Should Be Terminated ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207D2821999-05-27027 May 1999 Requests That Implementation Date for Unit 1 Be Changed Prior to Startup for L1C10 to Allow Best Allocation of Resources to Implement Unit 1 Amend Prior to Startup for Either L1C9 or L1C10.Unit 2 Will Implement Mod IAW Request ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20206R4561999-05-12012 May 1999 Provides Notification That Ws Jakielski,License SOP-30168-3, Is Being Reassigned & No Longer Requires Use of NRC License, IAW 10CFR50.74 ML20206K7081999-05-0707 May 1999 Forwards 10CFR50.46(a)(3) Rept Re Significant Change in Calculated Pct.Loca Analyses for Both GE Fuel & Siemens Power Corp Fuel Demonstrates Results within All of Acceptance Criteria Set Forth in 10CFR50.46 05000373/LER-1999-001, Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii).Attachment a Provides Commitments for Submittal1999-05-0707 May 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii).Attachment a Provides Commitments for Submittal ML20206K1861999-04-30030 April 1999 Informs That in Comed Submitted Annual Exposure Rept for Personnel Receiving Greater than 0 Mrem/Yr Rather than 100 Mrem/Yr.Updated Rept Limiting Data to Personnel Receiving Greater than 100 Mrem/Yr,Attached ML20206F0931999-04-30030 April 1999 Forwards LaSalle County Nuclear Power Station,Units 1 & 2 Effluent & Waste Disposal Semi-Annual Rept for 1998. LaSalle County Station Tech Specs Recently Revised to Reduce Periodicity of 10CFR50.36a ML20206R0751999-04-30030 April 1999 Forwards License Renewal Applications & Certification of Medical Examinations for LaSalle County Station Personnel Whose Licenses Expire in Nov.Personnel Listed.Without Encls ML20206D5921999-04-28028 April 1999 Forwards Annual Environ Operating Rept for 1998 for Environ Protection Plan, for LaSalle County Station,Units 1 & 2. Rept Includes Info Required by Listed Subsections of App B to Licenses NPF-11 & NPF-18 ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205L8161999-04-0808 April 1999 Advises NRC of Util Review & Approval of Cycle 8 Reload Under Provisions of 10CFR50.59 & Transmit COLR for Upcoming Cycle Consistent with GL 88-16.Reload Licensing Analyses Performed for Cycle 8 Utilize NRC-approved Methodologies ML20205J9451999-04-0505 April 1999 Submits Petition Per 10CFR2.206 Requesting That LaSalle County Nuclear Plant Be Immediately Shut Down & OL Suspended or Modified Until Such Time That Facility Design & Licensing Bases Are Properly Updated ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207J9841999-03-0505 March 1999 Informs That Effective 990212,KC Dorwick Has Resigned & No Longer Requires Use of NRC License for LaSalle County Station ML20207C7251999-03-0101 March 1999 Forwards Annual Rept for LaSalle County Station, for Period of 980101-981231.App E to Rept Provides Info on All Personnel Receiving Exposures of More than 0 Mrem/Yr Rather than 100 Mrem/Yr Requirement of TS 6.6.A.2 ML20207F9581999-03-0101 March 1999 Requests That Initial License Examination Currently Scheduled for Weeks of May 15 & 22,2000 Be Changed to Weeks of Nov 13 & 20,2000.Class Size Is Projected to Be Twelve RO & SRO Candidates ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207C8401999-02-25025 February 1999 Forwards Rev 60 of Comed LSCS Security Plan,Iaw 10CFR50.4(b) (4).Rev Eliminates Requirement for Annual change-out of Vital & PA Keys & Locks & re-configuration of PA Fence Around North Access Facility.Rev Withheld ML20207A9361999-02-24024 February 1999 Forwards Rev 4 to Restart Plan,To Reflect Review,Oversight & Approval Process Necessary to Restart Unit 2.Review & Affirmation Process Will Focus on Station Capability to Support Safe Dual Unit Operations 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059H5321990-09-11011 September 1990 Requests Withdrawal of Application for Amend to Licenses NPF-11 & NPF-18,per 891215 & s.Amend Would Have Removed Applicability of Tech Spec (TS) 3.0.4 to TS 3.6.5.2, Secondary Containment Automatic Isolation Dampers ML20059H4271990-09-0707 September 1990 Provides Supplemental Response to NRC Bulletin 90-001.Plant Initial Review of Calibr Records Completed on 900831 ML20059G0941990-09-0505 September 1990 Forwards LaSalle County Station Unit 2 Third Refueling Outage,Asme Section XI Summary Rept for Spring 1990 Insp ML20059C6891990-08-30030 August 1990 Forwards LaSalle County Nuclear Power Station Unit 2,Cycle 4 Startup Test Rept & Test Rept Summary ML20056B4061990-08-21021 August 1990 Submits Supplemental Response to Generic Ltr 88-14 Re Design & Verification of Instrument Air Sys.Mfg Purchase Specs & Vendor Manuals Reviewed for Air Quality Requirements ML20059B8961990-08-14014 August 1990 Documents Approval of Schedular Extension & Accepts Human Engineering Discrepancies Discussed ML20059D1731990-08-10010 August 1990 Responds to NRC Re Exercise Weaknesses Noted in Insp Repts 50-373/90-05 & 50-374/90-06.Corrective Actions: LOA-FP-01, Fire Alarm Response Will Be Revised to Alert Control Room Operators to Refer to Emergency Action Levels ML20058N2971990-08-0606 August 1990 Forwards Rev 34 to Security Plan.Rev Details Addl Gate Position for Security Testing & Maint.Rev Withheld (Ref 10CFR73.21) ML20064A5491990-07-27027 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-12 & 50-374/90-13.Corrective Actions:Program Implemented Identifying & Correcting Repetitive Local Leak Rate Failures Through Testing & LER Investigation ML20056A7031990-07-27027 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-13 & 50-374/90-14.Corrective actions:LRP-1250-3 Revised to Include Addl Requirement for Extremity Monitoring ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants ML20055H7661990-07-24024 July 1990 Forwards Supplemental Response to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML20055G2011990-07-13013 July 1990 Forwards Corrected Monthly Operating Rept for June 1990 for LaSalle County Unit 1.Outage/Reduction 16 Corrected ML20055F1831990-07-0909 July 1990 Provides Status Rept on Breaker Replacements in Response to NRC Bulletin 88-010.Breaker Replacements for Plants Scheduled to Be Completed by 901031 ML20044B1751990-07-0909 July 1990 Responds to NRC Request for Addl Info Re Util 890726 Proposed Amend to Tech Specs to Allow Continued Operation for Period of 12 H W/Main Steam Tunnel High Ambient Temp & High Ventilation Sys Differential Trips Bypassed ML17202L2861990-07-0202 July 1990 Forwards Dresden II Upper Vessel Contract Variation Review, La Salle II Upper Vessel Fabrication Summary & Quad-Cities II Upper Vessel Fabrication Summary. ML20055D1921990-06-29029 June 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues ML20055J2021990-06-26026 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-373/90-06 & 50-374/90-06.Corrective Actions:Perimeter Zone Repairs Commenced on Schedule & Completely Functional & Out of Compensatory Measures on 900614 ML20044A5071990-06-22022 June 1990 Forwards Revised Response to Station Blackout Rule for Plant.During Blackout Event,Plant Can Utilize RCIC Sys or HPCS to Provide Required Reactor Vessel Inventory Makeup ML20043E8651990-06-0707 June 1990 Forwards Relief Request RV-57 for Emergency Fuel Pool Makeup Crosstive Vent Valve 1(2)E12-F097.Expedious Review of Request Requested Because Valve 1(2)E12-F097 Inoperable & Will Remain So Until NRC Approval Received ML20043D3221990-06-0101 June 1990 Forwards Rev 33 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043C8241990-06-0101 June 1990 Advises of Intentions to Review & Approve Cycle 4 Reload,Per 10CFR50.59 & Forwards Rev 1 to LAP-1200-16, Core Operating Limits Repts for LaSalle County Station Unit 2,Reload 3, Cycle 4, Per Generic Ltr 88-16 ML20043B6581990-05-25025 May 1990 Requests Schedular Extension of Two Human Engineering Deficiencies Re CRT Displays W/Current Ramtek Sys & Approval to Leave Seven Human Engineering Discrepancies Accepted as Is. ML20043B7921990-05-23023 May 1990 Forwards Endorsements 14 to Nelia Policy N-71 & Maelu Policy M-71 & Endorsements 12 to Nelia & Maelu Policies N-83 & M-83,respectively ML20042E8841990-04-30030 April 1990 Responds to Generic Ltr 89-04 Re Weaknesses of Inservice Testing Programs.Plant Has Implemented Rev 2 of Inservice Testing Program Submitted by Util 891002 & 24 Ltrs.No Equipment Mods Required as Result of Generic Ltr ML20042F3591990-04-29029 April 1990 Provides Suppl Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Precaution Added to Operating Procedures Which Allows ECCS Pump to Be Secured & Restarted as Necessary to Preclude Running Pumps at Min Flow ML20042F0341990-04-23023 April 1990 Forwards Part 3 to 1989 Operating Rept,Containing Results of Radiological Environ & Meteorological Monitoring Programs. W/O Encl ML20064A6281990-03-30030 March 1990 Submits Supplemental Response to Insp Repts 50-373/86-04 & 50-374/86-04 Re Fire Detection Concerns,Per NRC 900214 Request.Proposed Administrative Controls & Training Will Eliminate Concerns That Assure Protection of Personnel ML20055E1461990-03-29029 March 1990 Provides Supplemental Response to Re Violations Noted in Insp Repts 50-373/89-18 & 50-374/89-18 on 890724- 0825.Corrective Actions:Plant Performs Safety Evaluation for Mods Not Designed by Corporate Nuclear Engineering Dept ML20012C6991990-03-15015 March 1990 Forwards Corrected Tech Spec Page to 881129 Application for Amend to Licenses NPF-11 & NPF-18,removing Specific Load Profiles for Each Dc Battery ML20012B6541990-02-26026 February 1990 Forwards LaSalle County Station Unit 1 Third Refueling Outage ASME Section XI Summary Rept, for Fall 1989 Inservice Insps Performed.Conditions Observed & Corrective Measures Taken Also Contained in Rept ML20006E7421990-02-0909 February 1990 Responds to NRC 900110 Ltr Re Violations Noted in Insp Repts 50-373/89-23 & 50-374/89-22.Corrective Actions:Ltr from Station Manager to All Dept Heads Was Issued on 891218, Discussing Personnel Performance Issues ML20005F5771990-01-0808 January 1990 Documents Guidance Given by P Shemanski Re Typos in Earlier Approved Amend to License NPF-11.Guidance Should Adhere to Wording of Unit 2 Tech Specs.Guidance Given on 900105 & Will Be Followed Until Correction Made at NRR Ofcs ML20011D9661989-12-22022 December 1989 Forwards Core Operating Limits Rept for LaSalle County Station Unit 1,Reload 3 (Cycle 4). Intention to Review & Approve Cycle 4 Reload Under Provisions of 10CFR50.59 Stated ML20005E1661989-12-22022 December 1989 Forwards Rev 32 to Security Plan,Reflecting Administrative Changes in Mgt Structure at Facilities.Rev Withheld (Ref 10CFR73.21) ML19332E4531989-11-29029 November 1989 Responds to Generic Ltr 89-21, Status of Implementation of USI Requirements. Response to USI A-48 Expected by 900319 ML19332C2461989-11-0808 November 1989 Provides Supplemental Response to Insp Repts 50-373/88-05 & 50-374/88-05 on 890302-10.Scheduled Completion Dates for Sample Panel Mods Changed from Third to Fourth Refueling Outages of Each Unit ML19325E5191989-10-31031 October 1989 Forwards Qualification Test Rept QTR87-018, Max Credible Fault Tests CM249-Q2 Carrier Modulator for Fermi 2 SPDS, in Response to NRC 890304 Request for Addl Info Re Facility Validyne Isolator CM-249 ML19325E3601989-10-26026 October 1989 Forwards Addl Info Re Application for Amend to Licenses NPF-11 & NPF-18,revising Tech Specs to Conform W/Diesel Generator Test Schedule Recommendations,Per Generic Ltr 84-15 ML19325E7921989-10-24024 October 1989 Submits Response to SALP 8 Board Repts 50-373/89-01 & 50-374/89-01.Expresses Appreciation for NRC Recognition of High Level of Performance in Area of Plant Operations, Emergency Preparedness & Security ML19325E0941989-10-24024 October 1989 Forwards Clarification to Summary of Changes Made in Rev 2 to Plant Inservice Testing Program ML19353A9051989-10-23023 October 1989 Responds to NRC 890921 Ltr Re Violations Noted in Insp Repts 50-373/89-19 & 50-374/89-19.Corrective Actions:Hose Connection That cross-connected Svc Air Sys W/Clean Condensate Sys Uncoupled & Secured ML17285A8081989-10-18018 October 1989 Responds to Request for Info on Environ Qualification of Taped Electrical Splices.Scotch Tapes Allowed by Electrical Test Guide Included Scotch 33,23 & 70 ML19325D1931989-10-13013 October 1989 Forwards Quarterly Rept on Static-O-Ring Failures Third Quarter 1989,per IE Bulletin 86-002.Stated Switches Replaced ML19327B0431989-10-0505 October 1989 Responds to NRC 890821 Ltr Re Violations Noted in Insp Repts 50-373/89-15 & 50-374/89-15.Corrective actions:post-order for Assembly Revised to Provide Specific Guidance on Use of Siren & Loudspeaker on Mobile Vehicles During Assemblies ML19327A7491989-10-0202 October 1989 Forwards Rev 2 to Combined Units 1 & 2 Inservice Testing Program for Pumps & Valves. Implementation of Program Will Require Procedure Revs Expected to Be Completed by 900228 ML19325D3271989-10-0202 October 1989 Forwards Rept Re Findings & Conclusions of Investigation Re 890826 Scram ML20248D0881989-09-21021 September 1989 Forwards Rev 56 to QA Program Topical Rept CE-1-A ML20247Q6431989-09-21021 September 1989 Documents Relaxation of Commitment Re Disassembling & Insp of Sor Switches ML19327A7681989-09-18018 September 1989 Forwards Response to Allegations Re Potential Employment Discrimination.Encl Withheld (Ref 10CFR2.790(a)(7)) 1990-09-07
[Table view] |
Text
.
. w x Commonwealth Edison
/ ) One First Nationti Plfzt, Chic 5go, Ilhnois k ~; Address Reply to Post Office Box 767
( / Chicago, Illinois 60690 February 21, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Units 1 and 2 Cable ?sparation Concerns NRC Docket Nos. 50-373 and 50-374 References (a): November 15, 1983 letter from C. W.
Schroeder to H. R. Denton.
(b): Section 7.3.3.2 and Appendix D LaSalle SSER #7, dated December, 1983.
Dear Mr. Denton:
This letter is to resolve the deficiencies described in Appendix D to Supplemental Safety Evaluation Report #7 regarding cable separation in Unit 1. The concern for cable separation in Unit 1 comes out of the License Condition for Unit 2. Item 2.c(10).
A detailed review and analysis was performed of the cable separation for enclosures containing reactor protection system cables.
Enclosed is Attachment A which contains a report of the analysis for Unit
- 1. Attachment A includes the criteria that has been used in the analysis and the justification on a panel-by-panel basis that the independence of the RPS circuits and channelization is not jeopardized.
Commonwealth Edison committed in Reference (a) to review the " Trip Report concerning cable separation concerns at LaSalle, Unit 2 (TIA-83-76)"
and address Sections 4.1, 4.2, 4.3, and 4.5 of that report. The review and analyses contained in Attachment A address the concerns of Sections 4.1 and 4.3.
Section 4.2 of Appendix D to LaSalle SSER #7 has been carefully reviewed. The concerns within this section have been identified, analyzed and accepted in the Regulatory Guide 1.75 response found in Appendix B of the LaSalle County Station FSAR. Attachment B to this letter identifies the applicable portion of the Reg Guide 1.75 response which covers Section 4.2 of Appendix D to the LaSalle SSER.
I gg22ggyg g 3 E l
- J
1 H. R. Denton February 21, 1986 l
Section 4.5 of Appendix D of SSER discusses redundant division cable separation for the solenoids mounted on the Automatic Depressurization System (ADS) relief valves. The initial cable design for the ADS valves required one division cabling to be enclosed in zipper tubing and the redundant division cabling terminated to the solenoid with no additional barrier. Commonwealth Edison has resolved this concern by the addition of zipper tubing to all divisional cabling associated with the ADS valves. We feel that this satisfactorily addresses the concerns identified in Section 4.5 of the SSER. The Unit 2 analysis is in progress and should be completed by May, 1986.
If you have any further questions on this matter, please contact this office.
One signed original and ten (10) copies of this letter and its attachments are being sent for your review.
Very truly yours, C. M. Allen Nuclear Licensing Administrator im Attachments A: Reactor Protection System (RPS) Cable Separation Analyses B: LaSalle County Station FSAR, Appendix B. Response'to Reg Guide 1.75, Pages B1-95 and B1-95a ec: Dr. A. Bournia - NRR LaSalle Resident Inspector 1326K a
ATTACHMENT A Pace 1 o'f'8 Reactor Protection Svatem (RP9)
Cable Senaration Analvsis Tne followino is a discussion of the analysis that was performed te justify the NRC Trip Report, concerning cable separation, dated November 4, 1983. Specifically, this discussion addresses Items 4.1(2)b, 4.l(2)c, 4.3(2):
TheindependenceofReactorProhectionSystem (RPS) circuits / channelization is not compromised for the fcllowing reasons:
A. RPS caoles of each channel are routed in separate raceways outside of control panels. The separation criteria for these raceways is provided on Sargent & Lundy Drawing IE-0-3333.
The separation of RPS cables from cables associated with safety-related divisions and non-safety-related cables inside control panels may be less than that dictated by IEEE-36*.
An analysis was performed to justify tne lesser separatior. of RPS cables from other cables inside of control panels. Th is analysis is discussed later.
B. All cables used to interconnect RPS are the same high cuality as that used in Class IE circuits, associated circuits, and non-safety related circuits. These types of cable comply with the requirements of IEEE 383-1974 and have been proven to be highly fire retardent by testing.
C. The cables that are a concern to the NRC are constrained to control and instrumentation circuits which, by their very nature, are low energy circuits. Control circuits are generally 120Vac or 125Vdc, whereas the- insulation rating of the cable utilized at LSCS for these applications is 600V.
D. There are no power cables in contact with the control and instrumentation cables that are in quest' ion. Also, there are no high energy sources located within control panels that contain RPS cables.
The independence of RPS circuits / channelization is not jeopardized inside control panels as demonstrated by an analysis which was performed for LSCS Unit 1. The following procedure was used to analyze all cables of the RPS systems 6
Reactor Protection System (RPS)
Cable Separation Analysis Page 2 of 8 Type 1 Identify non-safety-related cablea (both those that are routed in non-safety raceways and those that are routed in safety raceways) that are terminated in the same enclosure as an RPS channels cables and verify that they are not terminated with any redundant RPS channels cables on the other end.
Type 2 Identify Class LE cables that are terminated in the same enclosure as an RPS channels cable and verify that they are not terminated with any redundant RPS channels cables on the other end.
If in either Types 1 or 2 above, redundant RPS channels are potentially jeopardized by the presence of a non-safety or Class, LE cable, a specific review was performed taking into consideration the function of the circuits, location of the circuits, and items A, B, C and D above, regarding the types of cables used for these circuits.
In the La Salle County FSAR Appendix B response to Regulatory Guide 1.75, the separation of non-RPS cables is discussed. As indicated the types, ratings, energy limitations are discussed for the control and instrumentation cables that are a' part of this analysis. For the reasons provided in the La Salle response to Regulatory Guide 1.75, cables that are routed with non-safety and Class lE cables (that are Type 1 or 2) are not required to be analyzed. Only cables, which are terminated in the same -
enclosure with RPS cables and have the potential of bridging redundant RPS subchannels, were reviewed in the analyals. See Figure 1 for an example of the analysis that was performed.
The results of this analysis are summarized as follows:
I. Reactor Buildinq NRC Trip Report Items 4.l(2)b, 4.l(2)c
- 1. 1H22-P004 Local Instrument Rack RPS Subchannel - Al The single Type 1 cable in this panel is not terminated with RPS cables at its other end.
- 2. 1H22-P005 Local Instrument Rack RPS Subchannel - A2 The single Type 1 cable in this panel is not terminated with RPS cables at its other end.
O
Reactor Protection System (RPS)
Cable Separation Analysis Page 3 of d
- 3. lil22-P010 Local _J n st rument Rack RDS Subchannel - 32 The single Type 1 cable in this panel is not terminated with RPS cables at its other end.
- 4. lH22-P026_. Local Instrument Rack [
RPS Subchannel - B2 The single Type 1 cable in this panel is not terminated with RPS cables at itc other end.
5, 1H22-P027 Local Instrument Rack RPS Subchannel - B1 The Type 2 cables in this panel are not terminated with RPS cables at their other ends.
- 6. 1PLF5J Suporession Pool Temperature Monitorinq Power Suoply Cabinet RPS Subchannels - Al and B1 There are no Type 1 and/or Type 2 cables in this panel.
- 7. IPLF6J Suppression Pool Temperature Monitoring Power Suoply Cabinet RPS Subchannels - A2 and B2 There are no Type 1 and/or Type 2 cables in this panel.
II. Auxiliary Building - Auxiliary Electrical Eculement Room and Control Room NRC Trip Report Item 4.3 (2)
- 1. IPA 13J Div. 1 Isolation Logic Cabinet RPS Subchannel - B1 Many cables in this panel are Type 1 because a single RPS cable (No.1PCl42) is terminated in this panel. However, none of these Type 1 cables are terminated with the cable containing the redundant function which is cable No. IPC143.
- Reactor Protection System (RPS)
Cable Separation Analysis Pale 4 af 9
- 2. I P A 14.1 D i '.' . ? Isolation Loc'c Cabin?'-.
RPS Succnannel - 82 The Typo i cables in this panel are not terminated with RPS cables at their other ends.
- 3. 11113-P 601 noactor Coro coolin, Ppnal RPS subchannels - Al and A2 ( .N a t e 1) t The Type 1 cables in thic panol are not terniaated with RPS cables at their ethar ends.
- 4. 1H13-P603 Reactor Contrni Panel l RPS Subcnannels - AL, A2, BL,.and 32 (Note 2)
The Type 1 cables in this panol are not terminated with RPS cables at their other ends.
- 5. lH13-P608 Power Rance ?tonitortnq Cabinet O r's 1-5 RPS Subcnannels - A1, A2, B1, and B2 (Note 3)
Thoro are Typo 1 cables that torninate at 1913-P601 with redundant division RPS cables, however, all RPS cables at 1H13-P60 3 a re totminated in a' separate metallic onclosuro. ,
. 6. 1H13-P409 Ronctor Protection Svstom Channel Al ~~
i RPS Sunchannois - A1, et, and A2 (Note 4) 4 i
l Thore is a single cable (Type 1) that on the other
! end terminatos with cables of the redundant RPS j Divisions A2 and B2. However, this 125Vdc control
! circuit is protected by a fuse as well as a redundant circuit breaker. These panels are located in a protected area (main control room).
I 7. 1H13-P609 Roactor Protection System Channel A2 RPS Subchannels - A2 and B2 Thero is a single cablo (Type 1) terminated at the other end with a single RPS cable of redundant division (B1), however, this cable is not rodundant in function to those of this panol.
i 4
i i
5 4
{. .
I l
! Reactor Protection System (RPE)
Cable Separation Analysis Page 5 of 8 t
i l 8. lH13-P611 Reactor Protection System Chrin?1 D1
! RPS Subchannels - Al and D1 1
) a. There is. a single cable (Type 2) terminated at l the other end.with a Single RPS cablo of i
redundant division (B2) , howeiter, this cablo l is not redundant in function to those of this panel. .
) b. There are 4 cables (Type 1) terminated at the ,
j other end with redundant division RPS ca51os (Al and A2). However, these are alar.n ,
circuits which are low energy, and the panel: !
! are located in the control room which la l considered to be a protected area. !
)
j 9. 1H13-P611 Reactor Protection System Channel H2 '
RPS Subchannels - A2 and D2 i a. There is 'a single cable (Typo 2) terminated at
! the other end with a single RP3 cable of the
- redundant division (BL), however,.thic cable j i is not redundant in function to those of.;his '
{ panel.
! b. There are 4 cables (Type.1) terminated at the 3
other end with redundant division RPS cablas i (Al and A2) . However, these are alarm j circuits which are low energy, and the panels i
are located in the control room which in '
l considered to be a protected area.
l
} c. There is a single cable (Type 1) terminated at 1
the other end with RPS cables of redundant I '
division (A1) . However, this 125Vdc control l circuit is protected by a fune as well as a ;
i redundant circuit breaker. These panels are also located in the control room which is considered to be a protected area.
i
- 10. 1H13-P632 Leak Detection Div.1 Panel
,' RP8 Subchannels - Al and A2 (Note $)
. The Type 1 and/or Type 2 cables in this panel are
, not terminated with RPS cables at their other ends.
e
~
1, t! ,
o Reactor Protection Systcm (RPS)
Cablo Separation Analysis Paqe 6 of 3
- 11. 1Hl3-Pd42 Leak Detoction Div. 2 Panal RPS Subchannels - 81 and Di (Note 5) ,
The Type 1 and/or Typo 2 cables in this panel are not terminated with RPS cables at their other ends.
- 12. 1H13-P635 Rad. Monitorina Div. 1 Panet RPS Subchannels - Al and Bl There are many Typo 1 and/or Type 2 cables in this panel that are not terminated with HPS cablos at their other ends. Also, there are 8 cables (Type 1) terminated at the other end with redundant RPS cables ( A2 and B2). The other end for all of theno cables is panol 1H13-P636, the Division 2 radiation monitoring panel. Six of thoso cables are 21 Vdc used for neutron monitoring alarms.
Those circuits are protected by a fuso as well as a circuit breaker. The other 2 circuits are also low eneray used for alarms fed f rom the main annunci9 tor Cabinet IPA 03J. Both thoso nanels tro located in the control room which is considered to be a protected area.
- 13. 1H13-P636 Red. Monitorin, Oiv. 2 Panni RPS Subchannels - A2 and BT Soo panel 1H13-P635.
Notost
- 1. These redundant subchannels exist in separate soctions of this main control panel.
- 2. These redundant RPS subchannels are terminated in separate metallic enclosures.
- 3. These redundant RPS subchannels have physical separation by their termination in 5 separate bays and separation within each bay.
- 4. A single A2 cable is terminated with redundant subchannels At and B1; however, this cable is required for the backup scram valves which is not redundant to any Al and si cable terminated at this panel section.
- 5. The redundant RPG channels terminated in this panel are used for the main steam isolation valve (MSIV) control circuits.
This is acceptable per General Electric Separation Document No. 22A2988, Rev. 6.
. . .o. ,
Ifcactor Protection System (RPS)
Cablo Separation Analysis Pa ;c 7 c.' t:
1 o
i i
Control Room Panel Annunciator Cabinet j till3-PXXX I PAX.u h
0 No RPS 1
Cables
. +
1 1
1 I f Separate gr Division 1 i Conduit Safety-Related j Channel Tray & Conduit.
! B2 i
l i
! < r Type 1 Cable
- j. _. ..
I Cables terminated j Nunbel Sea Codo ,
! LPPXXX B2C 1
j .
i
! 1RSXXX 11K
. i 1RDXXX 12C i
I l j 1H22-P0XX i I
j Figure 1 Example RPS Separation Analysis i
e Reactor suilding 1.ocal Instrument Rack 1H22-P0XX
]
l .
j i
I -
a
- . 1 of 2 (rigure 1)
\
Reactor Protection System (RPS)
Cable Separation Analysis Paqe 3 of 3 Discussian: In this example, 2 non-sa fety related cables are terminated with a RPS subchannel B2 Cable 1RPXXX.
Cable IRDXXX seg. Code 12C is of the same nume ri'ca l division as of 1RPXXX and will not be considered because loss of a single division will not be capable of preventing a required RPS action. Cable IRSXXX Sea. Code 11K is opposite numerical diviaton to 1RPXXX (B2C) and for purposes of this analysis will be considered a Type 1 cable.
Result: The Type 1 cable in this panel is not terminated with RPS cablos at its other end. RPS channelization has not been denraded. (i.e. a fault in this cable cannot affect two redundant RPS subchannels) h 2 of 2 ( Figure 1)
o
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s NUCLEAR SAFETY RELAffD EQ@PMENT IS SHOWN ON TM5 ORAWNG
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LSCS-FSAR AMENDMENT 55 l
- ATTACHMENT 8 0
MARCH 1981 IEEE-384, Class lE circuits are not degraded below an '
acceptable level for the following reasons:
1
- a. Cables associated with one safety-related division are never routed in cable trays or conduit containing cables of a redundant safety-related division. This is true for all general. plant areas. Lesser separation than that dictated by IEEE-384 occurs only within control panels located in the control room and auxiliary equipment room.
b.
All cables used to interconnect associated circuits are the same high quality as that utilized in Class lE circuits, i.e., all associated cables comply with the requirements of IEEE 383-1974.
Therefore, this cable has been proven to be highly fire retardant by testing. ,
- c. Cables with separation less than that dictated by Sections 5.1.3 and 5.6. 2 of IEEE-384 are constrained to control and instrumentation circuits which, by their very nature, are low energy circuits. Control circuits are generally 120-Vac or 125-Vde, whereas, the insulation rating of the cable utilized at LSCS is 600-V.
- d. There are no power cables in contact with the control and instrumentation cables in the cable spreading area or in the control room and auxiliary equipment room. Also, there are no high energy sources located within control panels installed in these areas.
- e. Fire stops are installed in the. bottom entrances of all control panels.
With respect to the separation of non-Class lE from Class lE control and instrumentation circuits, LSCS complies with Section 4.6.2 of IEEE-384. Although the separation of non-Class lE from Class lE control and instrumentation circuits is in some cases, less than that required by Sections 5.1.3 and 5.6.2 of IEEE-384, these circuits have been analyzed to show that Class lE circuits are not degraded below an acceptable level because:
- a. Non-Class lE cables are routed in separate cable trays from Class 1E and associated cables in general plant areas.
- b. Non-Class lE cables which come in close proximity to Class lE and associated cables at one end do not come in contact with redundant Class lE or associated circuits at their other end.
This has been confirmed by a study of installed cables at LSCS.
B.1-95
1 LSCS-FSAR AMENDMENT 56 MAY 1981
' c. All cables u?ed to interconnect non-Class lE circuits are the same high quality as that utilized in Class lE circuits, i.e. , all asso-ciated cables comply with the requirements of IEEE 383-1974. Therefore, this cable has been proven to be highly fire retardant by testing.
- d. Cable separation less than that required by Sections 5.1 and 5.6 of IEEE-384 is limited to control and instrumentation circuits which by their very nature are low energy circuits. Control circuits are generally 120-Vac or 125-Vde, whereas, the insulation rating of the cable uti,lized at LSCS is 600-V.
- e. There are no power cables in contact with the control and instrumentation cables in the cable spreading area or in the control room.and auxiliary equipment room. Also, there are no high energy sources located within control panels installed in these areas.
- f. Fire stops are installed in the bottom entrances of all control panels.
Position cable and10raceway refers toidentification.
Section 5.1.2 of IEEE 384-1974 concerning The LSCS design utilizes cable trays with permanent colored-identification markers at each routing point which are assigned and alphanumeric code per Table 8.3-6 of the LSCS-FSAR. Each cable is assigned a number and segregation code. This information is placed on a colored tag, of permanent design, which is affixed to each end of the cable. A similar tag is also affixed to the cable where it enters and exits a penetration.
The LSCS 15, and 16. design complies with Positions 11, 12, 13, 14, IEEE 384-1974, Section 4.6, requires that Non-Class lE cable trays be separated from Class lE cable trays by the following minimum separation requirements:
- a. 1 ft horizuntally and 3 ft vertically in cable spreading areas,
- b. 3 ft horizontally and 5 ft vertically in general plant areas.
The La Salle County Station (LSCS) criteria specifies that the minimum distance between safety-related and non-safety-related cable trays shall be 3 inches horizontally and 1 foot vertically.
Cable trays at LSCS were installed to this specific criterion prior to issuance of IEEE-384.
B.1-95a